Makoto Nakamura

Employment

• Helical Fusion Chief Researcher
  2023 - Present
• National Institute of Technology, Kushiro College Associate professor
  2020 - 2023

Education

Education history is unavailable.

Projects & Funding

Projects & funding information is unavailable.

Publications (12)

• Thickness-variation measurement at downstream regions for Li target of fusion neutron sources
  Fusion Engineering and Design 2022 DOI: 10.1016/j.fusengdes.2022.113100
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• Conceptual design of advanced fusion neutron source (A-FNS) and irradiation test modules
  Nuclear Fusion 2021 DOI: 10.1088/1741-4326/ac21f6
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• Conceptual design progress of advanced fusion neutron source
  Nuclear Fusion 2021 DOI: 10.1088/1741-4326/ab9125
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• Interaction between surface behavior and inner flow pattern of liquid Li jet for fusion neutron sources
  Fusion Engineering and Design 2020 DOI: 10.1016/j.fusengdes.2020.111842
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• Verification of accuracy of contact-probe distance meter for lithium target of fusion neutron source
  Fusion Engineering and Design 2020 DOI: 10.1016/j.fusengdes.2020.111799
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• Conceptual design of test modules for DEMO blanket, diagnostic device, and RI production for A-FNS
  Fusion Engineering and Design 2020 DOI: 10.1016/j.fusengdes.2020.111632
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• Overview of test modules for Advanced Fusion Neutron Source A-FNS
  Fusion Engineering and Design 2020 DOI: 10.1016/j.fusengdes.2020.111714
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• Development of plant concept related to tritium handling in the water-cooling system for JA DEMO
  Fusion Engineering and Design 2019 DOI: 10.1016/j.fusengdes.2019.03.174
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• Modeling of chemical reactions of beryllium/beryllide pebbles with steam for hydrogen safety design of water-cooled DEMO
  Fusion Engineering and Design 2018 DOI: 10.1016/j.fusengdes.2018.05.039
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• Impact of the beam pressure on the free surface of the liquid lithium target of fusion neutron sources
  Nuclear Materials and Energy 2018 DOI: 10.1016/j.nme.2018.05.007
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• Thermal properties of beryllides as advanced neutron multipliers for DEMO fusion application
  Nuclear Materials and Energy 2018 DOI: 10.1016/j.nme.2018.02.002
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• Thermohydraulic Analysis of Accident Scenarios of a Fusion DEMO Reactor Based on Water-Cooled Ceramic Breeder Blanket: Analysis of LOCAs and LOVA
  IEEE Transactions on Plasma Science 2016 DOI: 10.1109/TPS.2016.2578348
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